ML17037B914
| ML17037B914 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/16/1977 |
| From: | Rhode G Niagara Mohawk Power Corp |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17037B914 (4) | |
Text
U.S. NUCLEAR REQULATORV COMMI N
NRC FoRM 195 I2 7E)
~'RC DlSTR)BUT)ON FQR'ART 50 DOCKET MATERlAL DOCKET NUMBER FILE NUMBER LETTER ABORIGINAL QCOr V DESCRIPTION Mr. Edson G.
Case ONOTORIEED UNCLASSIFIED PROP INPUT FORM ENCLOSURE FROM:
Niagara Mohawk
- Syracuse, N. Y.
13202 Gerald K. Rhode DATE OF DOCUMENT 12/16/77 DATE RECEIVED 12/19/77 NUMBER OF COPIES RECEIVED Furnishing response to NRC's ltr dtd 11/25/77
~. ~ consists of info concerning plan to resolve the potential problems with the relief valve circuit control for Nine Mil Point Unit g 2...
1p PLANT VIAME:
NINE MILE POINT UNIT g 2 jcm 12/21/77 FOR ACTION/INFORMATION ENVIROIPilENTAL CH CHIEF:
PROJECT MANAGER:
LIC ~ ASST:
AS5486S ASSIGNED AD:
BRANCH CHIEF:
(LTR FILES DR INTERNAL0 B.
HARLESS RI BUTION SYSTEMS SITE SAFETY G
ENVIRON ANALYSIS DENTON G MULLER SSICK G STAFF P
'4 VJAGEITENT LINS LPDR:
HAiVCHETT) l6 CYS SENT CATEGOR NRC FORM 195 (2 TS)
ENGINEERDIG ACTOR SAFETY ROSS NOVAK ROSZTOCZY CHECK L ZMAN EXTERNALOISTR IBUTION To AWS TO LER
,C 5CW CTORS NVIRON TECH ERNST BALLARD L
D TECH GAMMILL (2 VALYSIS VOLPIER VS CONTROL NUMBER
~~3SS0glg3
(
J
Nl V MIIASAQA lMU MQNIAWK Gerald K. Rhode NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 Vice President System Project Management December 16, 1977 Mr. Edson G.
- Case, Acting Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.
C.
20555 Re:
Nine Mile Point Unit 2 Docket No. 50-410
Dear Sir:
Mr. Varga's November 25, 1977 letter requested a plan to resolve the potential problems with the relief valve circuit control for Nine Mile Point Unit 2.
My November 17, 1977 letter to Mr.. Grier indicated that this design is being evaluated by the Mark II Containment Owners and the General Electric Company.
Additionally, we have discussed this matter with our architect engineer.
The potential problems with relief valve "second pop" will be evaluated in conjunction with the Mark II Containment Owners Group evaluations.
The loads associated. with this phenomenon will be identified and their impacts assessed.
Design changes, if any, will be described in. Revision 2 to the "Plant Design Assessment for Safety Relief Valve and Loss of Coolant Accident Loads."
Very truly yours, NIAGARA MOHAWK POWER CORPORATION rzp ral K.
ode NLR/szd 773550113
RE/if' y <<Q Qflg/Jpp ps'I,"gg'
'i"
'9V D C Ig +
9 23 0
J I
'r n